Browse "NE-Conference Papers(학술회의논문)" by Author 546
Showing results 104 to 163 of 205
| Effects of Inter-Assembly Spectral Interaction in MOX Cores Analyzed by CASMO-3M/AFEN Cho, Nam-Zin; Jo, C.K., Proc. of the Korean Nuclear Society Spring Meeting, pp.23 - 28, 1994-05 |
| Estimation of Flux Distribution via Observer Design Park, YH; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation Design and Computation, v.2, pp.59 - 68, 1990-04 |
| Estimation of the Fuel Depletion Code Bias and Uncertainty in Burnup-credit Criticality Analysis Kim, J.W; Cho, Nam-Zin; Lee, S.J; Baeg, C.Y, Proceedings of the Korean Nuclear Society Autumn Meeting, 2006-11 |
| Evaluation of Truncation Error in Minimal Cut Set-Based Fault Tree Analysis Choi, Jong Soo; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society Spring Meeting, 2005-10 |
| Evaluation of U-Zr Hydride Fuel for a Thorium Fuel Cycle in an RTR Concept Lee, K.T; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.52 - 57, 1998-05 |
| Extension of AFEN Methodology to Multigroup Problems in Hexagonal-Z Geometry Cho, Nam-Zin; Kim, Y.H; Park, K.W, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.137 - 141, 1996-05 |
| Fast Solution of Linear Systems by Wavelet Transform Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.282 - 287, 1996-05 |
| Feasibility and Characteristics of Graphite-Filled MOX Fuel Design for Full Loaded PWR Cores Jo, C.K; Cho, Nam-Zin; Kim, Y.H, International Conference on the Physics of Nuclear Science and Technology, pp.495 -, 1998-10 |
| Feasibility Study of Constant Composition TRU Feeding in an Accelerator-Driven Fluid-Fueled Thermal Reactor System Kim, D.S; Cho, Nam-Zin; Park, W.S, International Conference on the Physics of Nuclear Science and Technology, pp.1563 -, 1998-10 |
| Fine-lattice stochastic modeling of particle fuels in an HTGR unit fuel element Yu, H.; Cho, Nam-Zin, 2005 Annual Meeting - American Nuclear Society, v.92, pp.510 - 513, 2005-06-05 |
| FN-Based Nodal Transport Method in X-Y Geometry Hong, S.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.39 - 44, 1996-11 |
| Fuel Self-Sufficient and Low Proliferation Risk Multi-Recycling of Spent Fuel Cho, Nam-Zin; Hong, S.G; Kim, T.H, The 13th KAIF/KNS Annual Conference, pp.417 -, 1998-04 |
| Gaussian Function Neural Network-Based Self-Tuning control of KMRR Park, M.G; Cho, Nam-Zin, Proc. of the Korean Nuclear society Spring Meeting, pp.297 - 302, 1993-05 |
| Generating Nonnegative Multigroup Scattering Cross Sections with Monte Carlo Simulation Kim, Jong Woon; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05 |
| Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts via Monte Carlo Method Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.667 - 672, 1992-05 |
| Generation of Isotropic and Anisotropic Scattering Cross Sections for Boltzmann-Fokker- Planck Equation via Decomposition and Minimized RMS Errors Kim, J.W; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2001-10 |
| Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation Ahn, J.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.15 - 20, 1992-05 |
| Generation of the Analytic Solutions of the Multigroup Discrete Ordinates Transport Equation in Slab Geometry by Using Infinite Medium Green's Function Hong, S.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, v.1, pp.47 -, 1999-10 |
| Image Reconstruction in Emission Computed Tomography via Multigrid Wavelet-Based Natural Pixel Method Park, C.J; Cho, Nam-Zin, International Conference on the Physics of Nuclear Science and Technology, pp.1703 -, 1998-10 |
| Implementation of a Parallel Algorithm in 2-D Assembly Transport Calculation on a Transputer Cho, Nam-Zin; Song, J.S, Proc. of the International Symposium on Numerical Transprot Theory, Moscow, Russia, pp.72 - 75, 1992-05 |
| Improved features and verification of an AFEN method code in hexagonal-z 3-D geometry for neutron diffusion calculation Cho, N.Z.; Lee, J.; Kim, D.S.; Yang, C.Y.; Cho, Nam-Zin, 2005 Annual Meeting - American Nuclear Society, v.92, pp.514 - 516, 2005-06-05 |
| Improved Features of the AFEN Method in Hexagonal-Z 3-D Geometry for Neutron Diffusion Calculation Cho, Nam-Zin; Lee, Jaejun; Kim, Do Sam; Yang, Chae Yong; Jo, Jong Chull, Atomic Energy Society of Japan Spring Meeting, pp.391 - 391, 2005-03 |
| Improved Negative Fixup with Cell Rebalance for Boltzmann-Fokker-Planck Transport Equation Choi, Y.K; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05 |
| Infinite-Dimensional Observer Theory for Dynamic Estimation of Neutron Flux and Xenon Distributions Park, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Annual Meeting, pp.131 - 136, 1991-10 |
| Inter-Assembly Thermal Flux Gradient Correction of Homogenization Parameters Based on One-Dimensional Heterogeneous Interface Model Noh, J.M; Joo, H.K; Yoo, J.W; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05 |
| Intranodal Burnup Gradient Correction in Analytic Function Expansion Nodal (AFEN) Method Noh, J.M; Cho, Nam-Zin, International Conference on the Mathematics and Computations, Reactor Physics, and Environmental Analyses, pp.1435 - 1444, 1995-04 |
| KIGEN - A Computer Code for Decay Heat Calculation by Analytic Relations Cho, Nam-Zin; Lee, Y.J, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05 |
| MARADD - A Computer Code for Semi-Markov Reliability Analysis of Test/Repair Policies for Standby Safety Systems Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meetign, 1989-05 |
| MARAS - A Computer Code for Semi-Markov Reliability Analysis of Alternating Systems Lee, K.N; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
| Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation : Preliminary Results Na, W.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
| Molecular Dynamics Simulation of Thermomechanical Properties of Mononitride Nuclear Fuel Hong, Qian; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05 |
| Monte Carlo anchoring method for loosely-coupled k-eigenvalue problems Yun, S.; Cho, Nam-Zin, International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009, v.3, pp.1977 - 1990, 2009-05-03 |
| Monte Carlo Simulation Models for Randomly Distributed Particle Fuels with Packing Fraction Variability Based on a Sub-Fine Lattice System Cho, Nam-Zin; Hui, Yu, 2007 Annual Meeting of the Atomic Energy Society of Japan, 2007-03 |
| Monte Carlo space-time reactor kinetics method and its verification with time-dependent SN method Yun, S.; Kim, J.W.; Cho, Nam-Zin, International Conference on the Physics of Reactors 2008, PHYSOR 08, pp.739 - 746, 2008-09-14 |
| Multi-Recycleing of Spent Fuel with Low Proliferation Risk Greenspan, E; Cho, Nam-Zin; Hong, S.G; Kim, T.H; Kastenberg, W.E., International Conference on Emerging Nuclear Energy System, 1998-06 |
| Multigrid Wavelet-Based Natural Pixel Method for Image Reconstruction in Emission Computed Tomography Park, C.J; Park, J.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.2, pp.705 - 710, 1998-05 |
| Neutron Transport Assembly Calculation with Non-Zero Net Current Boundary Condition for Group Constant Generation Cho, Nam-Zin; Jo, C.K., Internation Conference on Reactor Physics and Reactor computations, 1994-01 |
| Neutronic Analysis of the KSTAR Tokamak Using Beowulf Cluster Park, J.H; Cho, Nam-Zin; Kim, J, Ninth International Conference on Radiation Shielding, pp.c2-16 -, 1999-10 |
| Neutronic Design Approach to a Small Medical Reactor for BNCT Cho, Nam-Zin, Proceedings of the 2000 Workshop on the Utilization of Research Reactors, 2000-11 |
| New features of the analytic function expansion nodal (AFEN) method and implementation in the hexagonal-Z KORDAX code Cho, Nam-Zin; Lee, J.; Kim, D.S.; Yang, C.Y.; Jo, J.C., 2004 Winter Meeting - American Nuclear Society, v.91, pp.257 - 260, 2004-11-14 |
| Nonlinear Model-Based Robust Control of a Nuclear Reactor Using Adaptive PIF Gains and Variable Structure Controller Park, M.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.285 - 290, 1992-10 |
| Nuclear and thermal analysis of shell-fuel pebble design based on the two-temperature homogenized model Yu, H.; Cho, Nam-Zin, 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.623 - 626, 2009-06-14 |
| Nuclear Data Compression and Reconstruction via Discrete Wavelet Transform Park, Y.R; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997-10 |
| Nuclear Energy Policy and R&D Prospects: The Korean Case Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation21, 1996-09 |
| On a New Acceleration Method for 3D Whole-Core Transport Calculations Cho, Nam-Zin; Lee, G.S; Park, C.J, Annual Meeting of the Atomic Energy Society of Japan, 2003-03 |
| On the AFEN Method for Triangular Nodes in Hexagonal Assembly Cores Cho, Nam-Zin; Kim, D.S., Proc. of the Korean Nuclear Society Spring Meeting, pp.25 - 30, 1995-05 |
| On the Multiplicity of Power Distributions in a Nuclear Reactor under Reactivity Feedback Effects Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1987-10 |
| One-Dimensional Heterogeneous Interface Model for Inter-Assembly Thermal Flux Gradient Correction of Homogenization Parameters Noh, J.M; Joo, H.K; Yoo, J.W; Cho, Nam-Zin, ANS Interanational Meeting on Mathematical Methods for Nuclear Applications (M&C 2001), 2001-09 |
| Online Self-Tuning Control of Korea Multipurpose Research Reactor Based on Gaussian Function Neural Network, Park, M.G.; Cho, Nam-Zin, Asian Symposium on Research Reactors, pp.157 - 166, 1993-11 |
| Optimal Control of Xenon Concentration via Observer Design Woo, H.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
| Overlap local/global iteration framework for Monte Carlo/diffusion nodal calculations Yun, S.; Lee, J.; Cho, Nam-Zin, 2010 ANS Annual Meeting and Embedded Topical Meetings, pp.528 - 532, 2010-06-13 |
| Pair Importance Measures in systems Analysis Youngblood, R; Xue, D; Cho, Nam-Zin, Proc. of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, San diego, California, v.2, pp.1 - 7, 1986-02 |
| Parallel Schwarz Algorithm for the Neutron Diffusion Equation on an MIMD Architecture Kim, Y.H; Cho, Nam-Zin, International Conference on Mathematical Methods and Supercomputing in Nuclear Applications, v.2, pp.100 - 111, 1993-04 |
| Parallel Sn Transport Calculation on a Transputer Network Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.29 - 34, 1994-05 |
| Pin Power Reconstruction from the HANARO Fuel Assembly Gamma Scanning Seo, C.G; Park, C.J; Cho, Nam-Zin; Kim, H.R, Proc. of the Korean Nuclear Society Autumn Meeting, pp.56 -, 1998 |
| Pin Power Reconstruction of HANARO Fuel Assembly via Gamma Scaning Cho, Nam-Zin; Fujine, S; Kobayashi, H; Kanda, K, Neutron Dadiography(6), pp.591 -, 2001 |
| Policies and Technology Development For the Nuclear Fuel Cycle in Korea Cho, Nam-Zin, College of Engineering Industrial Liaison Program 19th Annual Conference, pp.21 -, 1997-03 |
| Power Distributions in a Nuclear Reactor Core Under Various Operating Conditions and Their Safety Implications Yang, C.Y; Cho, Nam-Zin, Proc. of the international ENS/ANS Conference on thermal Reactor Safety, Avignon, France, v.4, pp.1314 - 1323, 1988-10 |
| Preconditioners for Krylov Iterative Method for Two-Dimensional MOC Problems Yoo, Han Jong; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society, 2007-10 |
| Preliminary Analysis on Decay Heat Removal Capability of Helium Cooled Solid Breeder Test Blanket Module Ahn, M.Y.; Cho, S.; Kim, D.H.; Lee, E.S.; Kim, H.S.; Suh, J.S.; Yun, S; et al, Proceedings of the Korean Nuclear Society, 2007-10 |
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Type
- 3 Article
- 5,616 Conference
Date issued
- 546 2020 - 2024
- 2,529 2010 - 2019
- 1,629 2000 - 2009
- 723 1990 - 1999
- 172 1980 - 1989